Contribution to optimal capacity utilization of unit 2 of the V-1 nuclear power plant

Data of the 7th, 8th and 9th fuel cycles of unit 2 of the V-1 nuclear power plant in Jaslovske Bohunice are used to analyze problems of reaching the rated capacity at the cycle beginning, associated with the problem of accurate determination of the primary circuit coolant water heatings. The method of corrected heatings has been used since January 1989; by means of this method, the correlation coefficients of temperatures at the reactor core outlet were established. This method is only a simplified approach to the problem of thermocouple aging in the reactor core and the associated problem of reaching the rated capacity. A more perfect approach to addressing this problem must proceed from a thermo-hydraulic analysis of the reactor core. In this sense it is also recommended to rebuild the measuring train, which requires installation of a high-performance 32-bit computer. (Z.M.). 3 figs., 2 tabs., 7 refs